ML20236A175

Insp Rept 50-285/89-12 on 890221-24.No Violations or Deviations Noted.Major Areas inspected:post-mod Testing & Followup on Main Steam Safety Valve Issue

ML20236A175
Person / Time
Site:	Fort Calhoun
Issue date:	03/07/1989
From:	Murphy M, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20236A172	List: ML20236A169 ML20236A175
References
50-285-89-12, NUDOCS 8903160438
Download: ML20236A175 (4)

See also: IR 05000285/1989012

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APPENDIX

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-285/89-12 Operating License: DPR-40

Docket: 50-285

Licensee: Omaha Public Power District (OPPD)

1623 Harney Street

Omaha, Nebraska 68102

Facility Name: Fort Calhoun Station (FCS)

Inspection At: FCS (Site), Blair, Nebraska

Inspection Conducted: February 21-24, 1989

Inspector: b M&--- 3/9'//1

M. E. Purpt[y', Reactor In!ipector Test Programs Date

Section Division of Reactor Safety

Approved: [ ' 3/7/#f

W. C. Seidle/ Chief, Test Programs Section Date

Division of Reactor Safety

Inspection Summary

Inspection Conducted February 21-24, 1989 (Report 50-285/89-121

Areas Inspected: Routine, unannounced inspection of post modification testing

and followup on the main steam safety valve issue.

Results: Within the areas inspected, no violations or deviations were

identified. The licensee's post modification testing was found to be in

conformance with the detailed design requirements. The testing acceptance

criteria were satisfactory and in conformance with Technical

Specifications (TS), regulatory requirements, and industry codes and standards.

The licensee has not identified the root cause of the three main steam safety

valves that failed to open during the last surveillance test (ST). The

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licensee does plan to modify or change the test method for the next ST.

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DETAILS

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1. Persons Contacted

OPPD

• C, Brunnert, Supervisor, Operations Quality Assurance (QA) .

• H. Faulhaber, Manager, Electrical Instrumentation and Control (180)

• J. Gasper Training Manager

• R. Jaworski, Manager, Station Engineering

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J.*Kecy, Supervisor, System Engineering

• L..Kusek, Acting Plant Menager

• D. Matthews,-Acting Supervisor, Station Licensing

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• R. Phelps, Manager, Design Engineering

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SWEC

B. Stecker, Test Engineer

NRC

P. Harrell, Senior Resident inspector

• T. Reis, Resident Inspector

The NRC inspector also interviewed other licensee employees during the

inspection.

• Denotes those attending the exit interview on February 24, 1989.

'2. Modification Testing (72701)

.The inspection was conducted to ascertain that the licensee's modification

testing program for new or modified structures, systems, and components

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was in conformance with detailed design documents, regulatory requirements,  !

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TS,'and industry codes and standards. The NRC inspector reviewed completed

Modifications 81-51, " Control Room Ventilation System Modification;" and u'81-064, " Reactor Coolant System Hot Leg Level Indication Modification."

Modification 81-51 increased the capacity of the control room air l

conditioning units so that only one unit is needed for operation. This

modification also eliminated unfiltered air leakage into the control room

and significantly reduced ambient heat gains to the system.

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Modification 81-064 was installed to prevent reaching a reactor coolant

' system level below that required for adequate suction head for the low

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pressure safety injection pumps during any shutdown and drained down

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condition. This modification replaced the present level indicator with a t

dual indicator. A "RCS Refueling Level Low" alarm was installed.

The review of these completed modifications determined that test

requirements were properly identified for component and system

construction phase testing. Wiring continuity and separation checks,

calibration of instrumentation and setpoints, and component functional

tests were satisfactorily accomplished.

The acceptance tests were conducted using procedures which contained the

appropriate features of scope, precautions, references, prerequisites,

acceptance criteria, tagouts, and system lineups. The procedures and

procedure change notices were reviewed and approved in accordance with the

licensee's administrative procedures. The licensee's review and

evaluation of the completed test procedures satisfactorily addressed that

the test results met the established acceptance criteria. Test problems

were resolved and retesting accomplished where required.

No violations or deviations were identified in this area of the

inspection.

3. Main Steam Safety Valves (MSSV) Setpoint Problem (92700) ,

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The NRC inspector reviewed Licensee Event Report (LER)88-023, which

reported the MSSV setpoint problem encountered during the last refueling

outage. While performing Surveillance Test (ST) ST-MSSV-1, " Main Steam

Safety Valve Test," four of the MSSVs failed their lift point test. One

valve was satisfactorily reset and retested.

Three of the valvos failed to lift even with maximum allowed test pressure

applied. These valves are Dresser Industries Maxiflow Model 6-inch

1500 psig class relief valves.

The licensee obtained concurrence from the vendor, issued a procedure

change, and manually cycled all three valves. The original ST was

l repeated and all three valves again failed to lift with maximum allowed

test pressure applied. The licensee uses the Hydrostet method for relief

valve testing with the system at normal operating temperature and

pressure.

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Subsequent to the second test attempt, the three valves were removed from

the system and sent to Wyle Laboratories. The laboratory was able to lift

all three valves, two were marginally out-of-specification high and one

was found to be in specification. All three valves were subsequently

found to exceed the post-lift seat leakage test and were refurbished by a

Dresser representative.

A review of previously reported MSSV setpoint problems reported in

LERs82-020, 84-002,85-006, and 87-003 did not reveal any pattern of

events.

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A review of the test reported in LER 88-023 did not reveal any sequence of

. events or personnel actions that would explain or provide leads to a

solution of the failure of the three valves to lift in situ. The licensee

is still attempting to determine the root cause and at this time is

studying the alternate test methods available to be used during the next

refueling outage.

No violations or deviations were identified in this area of the

inspection.

4 Exit Interview

The NRC inspector met with the personnel denoted in paragraph 1 on

February 24, 1989. The NRC inspector summarized the scope and findings of

the inspection. The licensee did not identify, as proprietary, any of the

infomation provided to, or reviewed by, the NRC inspector.